ML101940391
| ML101940391 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/12/2008 |
| From: | Kern R Automated Engineering Services Corp |
| To: | Florida Power & Light Co, Office of Nuclear Reactor Regulation |
| References | |
| PBNP-994-21-07, Rev. 0 | |
| Download: ML101940391 (8) | |
Text
ENCLOSURE 1 ATTACHMENT 17 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 LICENSE AMENDMENT REQUEST 261 EXTENDED POWER UPRATE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION PBNP-994-21-07, REVISION 0, HELB TASK 07 - MASS & ENERGY RELEASES FOR PRESSURE LIMITING CASES 7 pages follow
Automated CALCULATION SHEET Page: 4 of 7 Engineering Calc. No.:
Services Corp.
PBNP-994-21-07 Client: FP&L Energy Revision:
0 Station: Point Beach Nuclear Plant Prepared By: RC Kern Calc.
Title:
HELB Task 07 - Mass & Energy Releases for Pressure Limiting Cases Reviewed By: CD Henry Safety Related Yes 2
No D
Date: 11/12/2008 Table of Contents Section Title Page 1.
2.
3.
4.
5.
6 7.
8.
9.
Purpose Design Input Assumptions Acceptance Criteria Software Methodology Analysis Conclusions References 5
5 5
6 6
6 6
7 7
Attachment Title No. of Pages A
Calculation of M&E Data for Pressure Limiting Cases 2
Form 3.1-3 Rev. 2
Automated CALCULATION SHEET Page: 5 of 7 Engineering Calc. No.:
Services Corp.
PBNP-994-21-07 Client: FP&L Energy Revision:
0 Station: Point Beach Nuclear Plant Prepared By: RC Kern Calc.
Title:
HELB Task 07 - Mass & Energy Releases for Pressure Limiting Cases Reviewed By: CD Henry Safety Related Yes No Eli Date: 11/12/2008
- 1.
Purpose The purpose of Task 07 of the High Energy Line Break (HELB) Reconstitution Program as defined in Design Input (DI) 1 is to determine the mass and energy (M&E) release data for HELBs in the Primary Auxiliary Building of the Point Beach Nuclear Plant. The limiting HELBs have been defined in Task 06 (DI 2).
The M&E data are required for both pressure and temperature limiting cases. The pressure limiting cases are short term and are most limiting under Hot Zero Power conditions, and the associated M&E data are generated and documented in this calculation.
For temperature limiting cases Westinghouse developed the main steam at power M&Es. S&L developed the main steam at power M&Es for the break in the CCW heat exchanger room using Fanno.
AES developed the main steam M&Es for the hot standby conditions using the Henry-Fauske and Moody coorelations.
- 2.
Design Input The Design Input (DI) used in this analysis consists of the following:
- 1. AES Project Plan PBNP-994-21-01 "Project Plan for HELB Reconstitution Program" December 18, 2007.
Crack Size/Location".
- 3.
Assumptions
- 1. The thermal hydraulic conditions at the location of the break/crack are conservatively assumed to remain constant at their initial conditions.
- 2. The mass flux at the break/crack location is calculated using the Extended Henry-Fauske critical flow model for sub-cooled liquid conditions and the Moody critical flow model for saturated steam and liquid conditions. The implementations of these models are described in Sections IV.3.1 and IV.3.2 of Reference 1, respectively. The calculations of the mass fluxes were based on the functional fits described in Section IV.3.5 of Reference 1.
- 3. No credit is taken for isolation of the break/crack flow during the short period of duration until the peak pressure has been reached for these pressure limiting cases.
Form 3.1-3 Rev-2
Automated CALCULATION SHEET Page: 6 of 7 Engineering Calc. No.:
Services Corp.
PBNP-994-21-07 Client: FP&L Energy Revision:
0 Station: Point Beach Nuclear Plant Prepared By: RC Kern Calc.
Title:
HELB Task 07 - Mass & Energy Releases for Pressure Limiting Cases Reviewed By: CD Henry Safety Related Yes R
No EZ Date: 11/12/2008 Form 3.1-3 Rev. 2
Automated CALCULATION SHEET Page: 7 of 7 Z
Engineering Calc. No.:
Services Corp.
PBNP-994-21-07 Client: FP&L Energy Revision:
0 Station: Point Beach Nuclear Plant Prepared By: RC Kern Calc.
Title:
HELB Task 07 - Mass & Energy Releases for Pressure Limiting Cases Reviewed By: CD Henry Safety Related Yes EW No D Date: 11/12/2008
- 4.
Acceptance Criteria There are no acceptance criteria associated with the analyses documented in this calculation.
- 5.
Software No software was used in the calculations documented herein.
- 6.
Methodology The mass flux at the break/crack location is calculated using the Extended Henry-Fauske critical flow model for sub-cooled liquid conditions and the Moody critical flow model for saturated steam and liquid conditions. The implementations of these models are described in Sections IV.3.1 and IV.3.2 of Reference 1, respectively. The calculations of the mass fluxes were based on the functional fits described in Section IV.3.5 of Reference 1. The implementation of these functional fits consists of performing the polynomial summations as required by the appropriate equation and using the coefficients shown in the corresponding table. Reference 2 is used along with the fluid properties (absolute pressure and enthalpy) to determine whether the fluid is subcooled or saturated, and this establishes the appropriate equation to be used. This determination is reflected in the value assigned to the parameter ITYPE with 2 for subcooled and 3 for saturated.
- 7.
Analysis The M&E data to be used for input to the pressure limiting cases are calculated and documented in Attachment A using the methodology described in Section 6.
Form 3.1-3 Rev. 2 Form 3.1-3 Rev. 2
Automated CALCULATION SHEET Page: 8 of 7 Engineering Calc. No.:
Services Corp.
PBNP-994-21-07 Client: FP&L Energy Revision:
0 Station: Point Beach Nuclear Plant Prepared By: RC Kern Calc.
Title:
HELB Task 07 - Mass & Energy Releases for Pressure Limiting Cases Reviewed By: CD Henry Safety Related Yes El No El Date: 11/12/2008
- 8.
Conclusions The M&E data to be used for input to the pressure limiting cases are documented in Attachment A.
- 9.
References
- 1. "RETRAN-3D --- A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems Volume 1: Theory and Numerics" NP-7450(A), Volume 1, Revision 5 Research Project 889-10 Computer Code manual, July 2001.
- 2. ASME International Steam Tables for Industrial Use based on IAPWS Industrial Formulation 1997 for the Thermodynamic Properties of Water and Steam, published 2000.
Form 3.1-3 Rev. 2 Form 3.1-3 Rev. 2
Automated CALCULATION SHEET Page: A-1 I of A-2 Z'
Engineering Calc. No.:
Services Corp.
PBNP-994-21-07 Client: FP&L Energy Revision:
0 Station: Point Beach Nuclear Plant Prepared By: RC Kern Calc.
Title:
HELB Task 07 - Mass & Energy Releases for Pressure Limiting Cases Reviewed By: CD Henry Safety Related Yes El No D Date: 11/12/2008 Attachment A Calculation of M&E Data for Pressure Limiting Cases A. 1 Overview Description The methodology consists of calculating the mass flux for a given set of thermal hydraulic conditions at the location of the break which are assumed to be constant at their initial conditions (Assumption 1) using the critical flow models identified in Assumption 2. Then these mass fluxes are multiplied by the appropriate areas shown in Table 6.0-1 of DI 2. For the current analyses, no credit is taken for isolation of the break flow during the short period of duration until the peak pressure has been reached for these pressure limiting cases (Assumption 3).
A.2 Calculation of the Mass Fluxes There are four unique sets of thermal hydraulic conditions at the break locations as seen in Table 6.0-1 of DI 2. These conditions along with the information associated with the critical flow model used and the corresponding critical mass fluxes (G) are given in the following table. These calculations were performed using the methodology described in Section 6.
The pressure in psia is obtained by adding 15 to the values in psig shown in Table 6.0-1 of DI2.
Number Pressure (psia)
Enthalpy (BTU/Ibm)
ITYPE*
G (Ibm/ft2-s) 1 1020 1191 2
2135 2
895 438 3
15108 3
300 249 3
11679 4
1020 5461 3
8018
- ITYPE = 2 for Moody
= 3 for Extended Henry-Fauske Note 1: The enthalpy used for this calculation was 546 instead of 547 to force subcooled conditions and yield a conservative and slightly larger mass flux.
A-1
LK Automated CALCULATION SHEET Page: A-2 of A-2 Engineering Calc. No.:
Services Corp.
PBNP-994-21-07 Client: FP&L Energy Revision:
0 Station: Point Beach Nuclear Plant Prepared By: RC Kern Calc.
Title:
HELB Task 07 - Mass & Energy Releases for Pressure Limiting Cases Reviewed By: CD Henry Safety Related Yes E
No D
Date: 11/12/2008 A.3 Calculation of M&E Data The following table presents the results for the M&E calculations.
Rooms Break Size (ft2)
G (Ibm/ft2-s)
Mass Flow Enthalpy (Ibm/s)
(BTU/Ibm) 524 and 4.3303 2135 9245 1191 596 1 524 and 0.0513 2135 110 1191 596 1 524 and 0.0210 8018 168 547 596 1 301 and 2.6552 2135 5669 1191 583 1 301 and 0.2010 2135 429 1191 583 1 224 and 0.0513 2135 110 1191 122
- 140, 147, 0.0233 11679 272 249
- 146, 137, 144 and 145 360 0.0167 15108 252 438 237 0.0513 2135 110 1191 271 and 0.0012 2135 3
1191 238 272 and 0.0444 2135 95 1191 273 Note 1 - Different sets of conditions are possible for the HELB in these rooms.
A-2